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"Clad failure modeling," R.G. Ballinger, R.A. Christensen, R.F. Eilbert, S.T.
Oldberg, E.T. Rumble and G.S Was, Zirconium in the Nuclear Industry: Fifth
Conference, D.G. Franklin (ed.), Am. Society for Testing and Materials, ASTM STP
754, 1982, pp. 129-145.
"Dealing with uncertainty in fuel rod modeling," S.T. Oldberg and R.A.
Christensen, Nuclear Technology, 1978, Vol. 37, pp. 40-47.
"Disaggregation of Line-of-Business data," R.A. Christensen and T.A.
Reichert, Technical Report, Entropy Limited, Belmont, MA, Oct. 26, 1974.
"Element-specific failure time estimation from ensemble statistics," R.A.
Christensen and E. Duchane, Fuel Rod Mechanical Performance Modeling, Task 3:
Fuel Rod Modeling and Decision Analysis, FRMPM32-2, July 27, 1979, Entropy
Minimax Sourcebook, 1981, Vol. 4, pp. 687-696.
"Entropy minimax analysis of simulated LOCA burst data," R.A. Christensen,
Report to U.S. Nuclear Regulatory Commission, AT(49-24)-0083, ELTD-74/1, NTIS
PB85-210151 Entropy Limited, Belmont, MA, Dec. 31, 1974, 32 pp.
"Entropy minimax hazard axes for failure analysis," R.A. Christensen, R.F.
Eilbert and S.T. Oldberg, Fuel Rod Mechanical Performance Modeling, Task 3: Fuel
Rod Modeling and Decision Analysis, FRMPM32-2, July 20, 1979, Entropy Minimax
Sourcebook, 1981, Vol. 4, pp. 673-684.
"Estimating chance correlation likelihood for hazard axis analysis," R.
Christensen and R. Eilbert, EPRI FRMPM33-2 and FRMPM34-1, Nov. 1979
[appears in Entropy Minimax Sourcebook, 1981, Vol. 4, pp. 711-731].
"Fission gas release and fuel reliability at extended burn up: predictions by
the SPEAR-BETA code," R.G. Ballinger, R.A. Christensen, R.F. Eilbert, S.T. Oldberg
and E.T. Rumble, Tech. Rept. EPRI RP971, Entropy Limited, Lincoln, MA, presented
at American Nuclear Society, Topical Meeting: LWR Extended Burnup-Fuel
Performance and Utilization, Williamsburg, VA, April 4-8, 1982.
"In-service predictions," R. Christensen and R. Ballinger, Joint EPRI/DOE
Fuel Performance Contractors' Overview Meeting, Atlanta, GA, April 8, 1980
[appears in Entropy Minimax Sourcebook, 1981, Vol. 4, pp. 79-81].
"Longitudinal distortion (bowing) of rods in nuclear fuel assemblies during
commerical reactor operations," R.A. Christensen, Sect. III.A.4 of "Entropy Minimax
Multivariate Statistical lModeling--II: Applications," Int. J. General System, 1986, Vol
12, pp. 260-261.
"Network formulation of the finite element method," R.A. Christensen, Int. J.
General Systems, 1988, Vol 14, pp. 59-75.
"Nuclear fuel rod failure hazard axes," R. Christensen, EPRI FRMPM33-2
and FRMPM34-1, Dec. 1979 [appears in Entropy Minimax Sourcebook, 1981, Vol.
4, pp. 699-708].
"Operating environment and design-specific component survival estimation
in aging nuclear power plants," A.J. Wolford and R.A. Christensen, Report to U.S.
Nuclear Regulatory Commission, Div. of Engineering, Office of Nuclear Regulatory
Research, EG&G Idaho, Inc., Idaho Falls, ID, April 1989, 29pp.
"Predictive modeling for failure analysis and product design," R.A.
Christensen, Watson School of Continuing Education, State Univ. of New York,
Binghamton, NY, March 13-14, 1985.
"Predictive modeling for failure analysis, product design and quality control,"
R.A. Christensen, State-of-the-Art Technology for Reliability Engineering, Office of